IR 05000429/2006003

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Insp Repts 50-440/85-22 & 50-441/85-12 on 850429-0603.No Violations or Significant Safety Issues Noted.Major Areas Inspected:Previous Insp Findings,Ser Followup Items & Preoperational Test Program Implementation
ML20127P732
Person / Time
Site: Perry, 05000429  FirstEnergy icon.png
Issue date: 06/26/1985
From: Knop R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20127P678 List:
References
50-440-85-22, 50-441-85-12, NUDOCS 8507020498
Download: ML20127P732 (9)
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NUCLEAR REGULATORY COMMISSION

REGION III

Reports No. 50-440/85022(DRP); 50-441/85012(DRP)

Docket Nos. 50-440; 50-441 Licenses No. CPPR-148; CPPR-149

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Licensee: Cleveland Electric Illuminating Company

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Post Office Box 5000 Cleveland, OH 44101 Facility Name: Perry Nuclear Power Plant, Units 1 and 2 Inspection At: Perry Site, Perry, OH Inspection Conducted: April 29 through June 3, 1985 Inspectors: J. A. Grobe

J. P. Brown, J "-

Approved By:

(JCC R. C. Knop, Chief b v,6 g f Reactor Projects Section 1C Date Inspection Summary Inspection on April 29 through June 3, 1985 (Report No. 50-440/85022(DRP);

50-441/85012(DRP))

Areas Inspected: Routine unannounced inspection by resident inspectors of previous inspection findings, Safety Evaluation Report followup items, preoperational test program implementation, safety committee activity, Unit 1 drywell fire, comparison of as-built plant to FSAR description, operation procedures and technical specifications. The inspection involved a total of 289 inspector-hours onsite by two h3C inspectors including 21 inspector-hours onsite during off-shift Results: Of the eight areas inspected, no violations were identified in any area. No significant safety issues were identifie PDR ADOCK 05000440

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e DETAILS Persons Contacted

  • M. D. Lyster, Manager, Perry Plant Operations Department
  • J. Waldron, Manager, Perry Plant Technical Department
  • C. M. Shuster, Manager, Quality Assurance Department
  • F. R. Stead, Manager, Nuclear Engineering Department
  • G. R. Leidich, General Supervising Engineer, Nuclear Test Section
  • B. D. Walrath, General Supervising Engineer, Operational Quality Section The inspectors also contacted numerous other applicant representatives during the inspection perio * Denotes those persons attending one or more of the exit interviews conducted on May 28 and 30, 198 . Applicant Action on Previous Inspection Findings (Closed) Open Inspection Item (440/85002-08(DRP)): Clarification of regulatory guide conformance documented in Final Safety Analysis Report (FSAR), Table The applicant responded to this open item with letters dated February 6, 1985, (PY-CEI/NRR-0177L), April 2, 1985, (PY-CEI/NRR-0222L), and May 14, 1985, (PY-CEI/NRR-0248L). The final letter included a proposed revision to FSAR pages for Section Regarding Table 1.8-1, "Conformance to NRC Regulatory Guides," the revised Section 1.8 states that " Conform as used in Table 1.8-1 means that PNPP has implemented the regulatory guides, to the extent described in the table and in the referenced FSAR sections." During discussions of this proposed revision with the applicant, the Nuclear Engineering Department Manager stated that the recommendations of each regulatory guide referenced in Table 1.8-1 would be fully implemented unless specific exception to a certain recommendation of that guide is documented in either the table or the FSAR section(s) referenced in the table. The inspector has no further concerns in this area. NRR and Region III personnel are currently reviewing their submittals. Any issues resulting from these reviews will be tracked separatel . Safety Evaluation Report Followup Inspection Items The Office of Nuclear Reactor Regulation has requested that Region III

! inspectors confirm that the applicant has acceptably implemented certain Three Mile Island (TMI) action items and confirmatory issues as described in the Safety Evaluation Report (SER) for PNPP, Unit 1 (NUREG 0887 with Supplements 1 through 6). Each of the items requiring inspection have

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been assigned an open item tracking number as listed below. Additionally, the SER reference section is noted in parenthesis.

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, (0 pen) Open Inspection Item (440/85022-01(DRP)): TMI Item I.A.1.1; j Verify that the applicant has implemented the on-shift technical advisor.

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(0 pen) Open Inspection Item (440/85022-02(DRP)): TMI Items I.A.1.2 and I.C.3; Determine that the shift supervisor's administrative duties are established to reduce his ancillary responsibilitie (SER 13.5.1.8)

(0 pen) Open Inspection Item (440/85022-03(DRP)): TMI Item I.A.1.3; Verify that shift manning restrictions have been establishe (SER 13.1.2.2 and 13.5.1.4)

(0 pen) Open Inspection Item (440/85022-04(DRS)): TMI Items I.A.2.1, I.A.2.3, and I.A.3.1; Determine that training and qualifications of applicant personnel have been establishe (SER 13.2.1)

(0 pen) Open Inspection Item (440/85022-05(DRP)): TMI Item I.A.2.2; Review training programs for all operations personnel, including ,/

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maintenance and technical personnel, to verify that programs have been ,,'

upgraded. (SER 13.5.1.5) ,-

(0 pen) Open Inspection Item (440/85022-06(DRP)): TMI Item I.B.1,2; Determine that the applicant has established an independent safety engineering group. (SER 13.4.2 and 13.5.1.6) -

(Open) Open Inspection Item (440/85022-07(DRP)): TMI Items I.C.1 and I.C.9; Determine that the applicant has provided proper procedures for normal, transient, and accident condition (SER 4.4.7.2, 6.3.3, and 13.5.2.2 and SSER3 13.5.2.2)

(0 pen) Open Inspection Item (440/85022-08(DRP)): TMI Item I.C.2; Determine that the applicant has established appropriate procedures for shift and relief turnove (SER 13.5.1.7)

(0 pen) Open Inspection Item (440/85022-09(DRP)): TMI Item I.C.4; Determine that procedures have been established to limit access to the control roo (SER 13.5.1.9)

(0 pen) Open Inspection Item (440/85022-10(DRP)): TMI Item I.C.5; Determine that procedures have been established to provide operating experience to the staf (SER 13.5.1.10)

(0 pen) Open Inspection Item (440/85022-11(DRP)): TMI Item I.C.6; Determine that controls have been established for verification of correct performance of operating activitie (SER 13.5.1.11 and SSER2 13.5.1.11)

(Open) Open Inspection Item (440/85022-12(DRS)): TMI Item I.C.7; Determine that the nuclear steam supply system vendor reviews low power and power ascension tests and emergency procedures (SER 13.5.2.2)

, (0 pen) Open Inspection Item (440/85022-13(DRP)): TMI Item I.G.1; Determine that additional training is given during low power testin (SER 14, Page 14-4, Item 5)

(0 pen) Open Inspection Item (440/85022-14(DRP)): TMI Item II.B.1; Verify that overpressure protection has been installed and teste (SER 5.2.3)

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(0 pen) Open Inspection Item (440/85022-15(DRSS): TMI Item II.B.2; Verify that the applicant has installed shieldin (SER 12.3.2 and SSER 2 12.3.2)

(0 pen) Open Inspection Item (440/85022-16(DRSS)): TMI Item II.B.3; Verify that the post accident sampling system has been installe (SER 9. and SSER4 9.3.2)

(0 pen) Open Inspection Item (440/85022-17(DRP)): TMI Item II.B.4; Verify that the training program for mitigating core damage has been implemente (SER 13.2.1)

(0 pen) Open Inspection Item (440/85022-18(DRS)): TMI Items II.D.1 and II.K.3.16; Verify that testing of relief and safety valves has been completed. (SER 3.9.3.2.1, 5.2.3, and 5.2.4)

(0 pen) Open Inspection Item (440/85022-19(DRS)): TMI Item II.D.3; Verify that position indication of relief and safety valves has been provided (SER 7.5.2.1)

(Open) Open Inspection Item (440/85022-20(DRS)): TMI Item II.E.4.2; Determine that containment isolation is complet (SER 3.9.3.2.1 and 6.2.7 and SSER2 6.2.7)

(0 pen) Open Inspection Item (440/85022-21(DRSS)): TMI Items II.F.1.1 and II.F.1.2; Determine that noble gas monitors with extended range and iodine / particulate monitoring have been installe (SER and SSER3 11.5)

(0 pen) Open Inspection Item (440/85022-22(DRSS)): TMI Item II.F.1.3; Verify that in-containment high-level radiation monitors have been installe (SER 12.3.4.1)

(0 pen) Open Inspection Item (440/85022-23(DRP)): TMI Items II.F.1.4, II.F.1.5, and II.F.1.6; Verify that instruments have been installed to monitor containment pressure, water level and hydroge (SER and SSER2 7.5.2.5)

(0 pen) Open Inspection Item (440/85022-24(DRP)): TMI Item II.F.2; Verify that instrumentation for detecting inadequate core cooling have been installe (SER, SSER3, and SSERS 4.4.7)

(Open) Open Inspection Item (440/85022-25(DRP)): TMI Item II.F.3; Verify thst instrumentation for monitoring accident conditions has been installe (SER, SSERS, and SSER6 7.5.2.2)

(0 pen) Open Inspection Item (440/85022-26(DRP)): TMI Item II.K.1.5; Deter.nine that engineered safety feature valves have position indication and other contro (SER 13.5.2.3. Also see IEB 79-05, 79-06, and 79-08)

(Open) Open Inspection Item (440/85022-27(DRP)): TMI Item II.K.1.10; Verify that controls have been instituted to ensure that critical valves'

operability status is know (SER 13.5. Also see IEB 79-05, 79-06, and 79-08)

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(0 pen) Open Inspection Item (440/85022-28(DRS)): TMI Item II.K.1.22; Verify that the residual heat removal testing is adequat (SER 5.4.2)

(Open) Open Inspection Item (440/85022-29(DRS)): TMI Item II.K.1.23; Verify that the testing of the reactor vessel level instrumentation is adequat (SER 13.5.2.6)

(0 pen) Open Inspection Item (440/85022-30(DRP)): TMI Item II.K.3.3; Determine that controls are in place to report safety and relief valve failures and challenge (SER 13.5.2.5)

(0 pen) Open Inspection Item (440/85022-31(DRP)): TMI Item II.K.3.17; Determine that controls are in place to report emergency core cooling system outage (SER 6.3.3)

(0 pen) Open Inspection Item (440/85022-32(DRS)): TMI Item II.K.3.18; Verify that testing confirms statements made with regard to automatic depressurization system logic modification (SSER1 6.3.3 and SSER4 6.3.1.3)

(0 pen) Open Inspection Item (440/85022-33(DRS)): TMI Item II.K.3.21; Determine that testing was conducted of the capabilities of the core spray and low pressure coolant injection system (SER 7.3.2.1)

(0 pen) Open Inspection Item (440/85022-34(DRS)): TMI Item II.K 3.24; Determine that adequate testing of the space coolers was performed for high pressure core spray and reactor core isolation cooling system room (SER 9.4.5.3)

(0 pen) Open Inspection Item (440/85022-35(DRP)): TMI Item III.D.1.1; Determine that procedures are in place to monitor coolant leakage outside containment before full-power operatio (SER 11.5)

(0 pen) Open Inspection Item (440/85022-36(DRSS)): TMI Item II.D.3.3; Verify that equipment is in place and training complete to monitor inplant iodine radiatio (SER 12.5.2)

(Open) Open Inspection Item (440/85022-37(DRP)): TMI Item III.D.3.4; Determine that equipment to ensure control room hibitability has been provide (SER 6.4)

(0 pen) Open Inspection Item (440/85022-38(DRS)): Confirmatory Issue 9 (SER 1.10); Verify proper criteria were used by the applicant for determining the design and construction of dual-function pipe whip / support restraint (SER 3.9.3.3)

(0 pen) Open Inspection Item (440/85022-39(DRS)): Confirmatory Issue 15 (SER 1.10); Determine that proper preservice and inservice inspection programs are implemente (SSERS 5.2.5 and 6.6.3)

(0 pen) Open Inspection Item (440/85022-40(DRS)): Confirmatory Issue 24 (SER 1.10); Determine that Type C leak rate testing of emergency core cooling system injection valves is conducte (SSER2 6.2.6)

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l (0 pen) Open Inspection Item (440/85022-41(DRS)): Confirmatory Issue 26 (SER 1.10); Verify that the anticipated transient without scram recirculation pump trip is teste (SSER4 7.2.2.3)

(0 pen) Open Inspection Item (440/85022-42(DRP)): Confirmatory Issue 27

(SER 1.10); Determine that the scram discharge volume level monitoring system has been installed and teste (SSER4 7.2.2.4)

(0 pen) Open Inspection Item (440/85022-43(DRS)): Confirmatory Issue 30 (SER 1.10); Determine that reactor core isolation cooling system testing

is properly performed. (SSER2 7.4.2.4)

! (0 pen) Open Inspection Item (440/85022-44(DRS)): Confirmatory Issue 31 (SER 1.10); Determine that proper calibration was performed for relief and safety valve pressure switches. (SER 7.5.2.1)

These issues will be examined during a future inspection. No items of noncompliance or deviations were identified in this are j Preoperational Test Program Implementation Verification

The inspector observed control room operation and test coordination, reviewed applicable logbooks and conducted discussions with control room

operators and test personnel during the it.v ection period to ensure that j test activities were being conducted in accordance with regulatory

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requirements and facility procedures. Tours of the Unit i reactor building, intermediate building, Unit 1 auxiliary building, fuel handling building, control complex and diesel generator building were conducted to observe test and maintenance work in progress, area housekeeping,

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equipment condition and system cleanliness. The inspector also reviewed tha minutes from Test Program Review Committee (TPRC) meetings No. 394 tr th 403, 405 and 406 conducted during this inspection period to ve. .y conformance with Nuclear Test Section procedures.

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No items of noncompliance or deviations were identified in this are . Safety Committee Activity The inspector attended Plant Operations Review Committee (PORC) meetings

No. 85-30, 85-39 and 85-41, and reviewed the minutes of meetings No.

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85-30 through 85-42, conducted during the inspection period to verify conformance with PNPP procedures and regulatory requirements. The i

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observations and examinations included PORC membership and qualifications, quorum at PORC meetings and PORC activitie No items of noncompliance or deviations were identified in this are ; Unit 1 Drywell Fire At approximately 2:05 a.m. on May 5, 1985, there was a fire in the Unit 1 l drywell involving wood that had been placed on top of the reactor vessel insulation above the biological shield wall just below the refueling

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cavity bellows seal. The wood was being used to protect the insulation from mechanical damage. By 2:30 a.m. the applicant requested the assistance of the offsite fire department. Perry Township Fire Department responded by 2:35 a.m. and began setting up to fight the fir By 5:00 a.m. the fire had been extinguished using pressurized water extinguishers and removal of damaged wood began. The inspector examined the fire scene on May 5, 1985, and noted little visible damage to permanent equipment. The apparent cause of the fire was combustible materials in too close proximity to hot process piping. The applicant's immediate corrective action, including initiation of Condition Report N , appeared adequate. The inspector will examine the completed condition report and resultant nonconformance reports during a future inspection. This will be tracked as an open item (440/85022-45(DRP)).

No items of noncompliance or deviations were identified in this are . Comparison of As-Built Plant to FSAR Description The inspector examined the Low Pressure Core Spray System (LPCS), the Safety Related Instrument Air System (SRIA) and the Residual Heat Removal (RHR) Subsystems A and C (low pressure coolant injection, containment spray and suppression pool cooling modes only), to verify that the as built mechanical configuration of the systems is as described in the controlled facility drawings including posted design change documents and the FSAR drawings. The inspector examined the following piping and instrumentation diagrams including posted Engineering Changes Notices (ECN) for those systems:

. D-302-705, Revision G, " Low Pressure Core Spray System"

. D-302-605, Revision D, " Nuclear Boiler System"

. D-302-271, Revision B, " Safety-Related Instrument Air System"

. D-302-641, Revision H, " Residual Heat Removal System"

. D-302-642, Revision H, " Residual Heat Removal System"

. D-302-643, Revision H, " Residual Heat Removal System" The inspector then compared those site controlled P& ids to the appropriate FSAR P& ids. Many minor discrepancies were noted in the FSAR due to posted design changes. The applicant had previously committed to provide updated P& ids in the last FSAR amendment prior to fuel load. The inspector will examine a sample of those updated drawings when the FSAR is amende This issue will be tracked as an open inspection item (440/85022-46(DRP)).

Following the FSAR comparison, the inspector used the site controlled P&ID and walked down the system to verify as built configuratio Several discrepancies were noted in each system as noted belo . -

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SYSTEM DISCREPANCY ITEM TYPE LPCS Pump suction vent flange not shown Unresolved Stop check valve F528 shown as Unresolved check valve SRIA Three relief valves were missing their Open discharge pipe stub (F513A, F513B and F520B)

Twenty-five pipe caps were missing Open Two permanent valve identification tags Open were missing (F0208 and F527B)

RHR The sensing lines for two pressure trans- Unresolved mitters were reversed (N050A and N051A)

One valve was not shown (F584A) Unresolved Ten permanent identification tags were Open missing Seven pipe caps were missing Open These discrepancies will be followed up under either unresolved item (440/85022-47(DRP)) or open inspection item (440/85022-48(DRP)).

No items of noncompliance or deviations were identified in this are . Operating Procedures The inspector examined the valve lineup instruction (VLI) for the Low Pressure Core Spray System (LPCS), VLI-E21, Revision 2, issued May 19, 1985, utilizing the information on the LPCS piping and instru-mentation diagram (P&ID), D-302-705, Revision G. The following discrepancies were noted:

VALVE NUMB _ER P&ID INDICATION VLI INDICATION F502 Closed Lock Closed F503 Locked Closed Closed F514 Closed Not Mentioned F507 Open* Closed F526 Locked Closed Closed

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F516 Closed / Cap Installed Closed F528 Not Indicated Closed

  • Reference Engineering Change Notice 2501 The inspector discussed these findings with the instruction author and found that the same discrepancies had already been identified by the applicant and were being addresse During walkdown of the LPCS valves, the inspector noted an inconsistency on the tagging for F528. The VLI indicates the valve is the

"lE21F528-F006 Test Line Stop Check Valve," however, the permanent valve identification tag indicates the valve is "E31F484-F006 Valve Stem Leakoff Line Root." This tagging discrepancy will be tracked as an open inspection item (440/85022-49(DRP)). Technical Specification Review The inspector initiated a detailed review of the " Proof and Review" technical specifications. The first major set of comments was forwarded to the Office of Nuclear Reactor Regulation by memorandum dated June 11, 1985, from C. E. Norelius to D. M. Crutchfield. Additional reviews of Section 3 and 4 of the proposed technical specifications will be conducted as preoperational and surveillance test reviews are complete No items of noncompliance or deviations were identifie . Open Inspection Items Open inspection items are matters which have been discussed with the applicant, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or the applicant or bot Open inspection items disclosed during the inspection are discussed in Paragraphs 3, 6, 7 and . Unresolved Inspection Items Unresolved items are matters which have been discussed with the applicant, which will be reviewed further by the inspector, and which involve some action on the part of the NRC or the applicant or both. Unresolved items disclosed during the inspection are discussed in Paragraph . Exit Interviews The inspectors met with applicant representatives denoted in Paragraph 1 throughout the inspection and at the conclusion of the inspection period on May 28 and 30, 1985. The inspectors summarized the scope and results of the inspection and discussed the likely content of this inspection report. The applicant did not indicate that any of the information disclosed during the inspection could be considered proprietary in natur

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